GB917402A - Process for the recovery and/or concentration of uranium and melt containing uranium - Google Patents

Process for the recovery and/or concentration of uranium and melt containing uranium

Info

Publication number
GB917402A
GB917402A GB2729859A GB2729859A GB917402A GB 917402 A GB917402 A GB 917402A GB 2729859 A GB2729859 A GB 2729859A GB 2729859 A GB2729859 A GB 2729859A GB 917402 A GB917402 A GB 917402A
Authority
GB
United Kingdom
Prior art keywords
melt
uranium
starting material
precipitate
molten
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
GB2729859A
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Dow Chemical Co
Original Assignee
Dow Chemical Co
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Dow Chemical Co filed Critical Dow Chemical Co
Publication of GB917402A publication Critical patent/GB917402A/en
Expired legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0213—Obtaining thorium, uranium, or other actinides obtaining uranium by dry processes
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/48—Non-aqueous processes
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Geology (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Environmental & Geological Engineering (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

U is purified by melting it with Al and Mg and separating the resultant precipitate of an intermetallic compound of U and Al from the molten Mg-Al alloy. The starting material, which is preferably an alloy or mixture of U and Al, is fused and Mg added. The melt is allowed to cool and held at within 200 DEG C. of the freezing point of the Mg-Al melt to allow precipitation of the U-Al intermetallic compound which is then separated from the melt by filtration in a suitably-designed furnace (see Group XII). Alternatively the melt is allowed to settle and solidify and the portion containing the U-Al compound cut from the remainder of the casting. The process may be repeated using the precipitate as starting material with or without further Al and the precipitate may be washed with molten Mg until the Al has been wholly or partly removed. The remaining Mg is then distilled off. U-compounds may be included in the starting material and their reduction effected by the Mg and/or Al added in the process.
GB2729859A 1958-08-26 1959-08-10 Process for the recovery and/or concentration of uranium and melt containing uranium Expired GB917402A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US75741958A 1958-08-26 1958-08-26

Publications (1)

Publication Number Publication Date
GB917402A true GB917402A (en) 1963-02-06

Family

ID=25047742

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2729859A Expired GB917402A (en) 1958-08-26 1959-08-10 Process for the recovery and/or concentration of uranium and melt containing uranium

Country Status (5)

Country Link
BE (1) BE584714A (en)
DE (1) DE1176371B (en)
FR (1) FR1248453A (en)
GB (1) GB917402A (en)
NL (1) NL242662A (en)

Also Published As

Publication number Publication date
DE1176371B (en) 1964-08-20
NL242662A (en) 1900-01-01
BE584714A (en) 1960-05-16
FR1248453A (en) 1960-12-16

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